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7442 U-007-409.10
SUPPLEMENTAL INFORMATION FOR THE ANNUAL RADIONUCLIDE AIR EMISSION REPORT FOR CALENDAR YEAR 1989, NATIONAL EMISSION STANDARDS AIR POLLUTANTS (NESHAP) - (USED AS A REFERENCE IN OU 5 FS, APPENDIX H - TITLE DIFFERS SLIGHTLY FROM CITATION IN REFERENCES)
0611 9/90
125 REPORT
SUPPLEMENTAL INFORMATION FOR THE ANNUAL RADIONUCLIDE
A I R EMISSION REPORT FOR CALENDAR YEAR 1989
NATIONAL EMISSION STANDARDS FOR HAZARDOUS A I R
POLLUTANTS (NESHAP) , 40 CFR 61, SUBPART H
FEED MATERIALS PRODUCTION CENTER
PLANT ADDRESS: FEED MATERIALS PRODUCTION CENTER 7400 WILLEY ROAD FERNALD, OHIO 45030
OWNER ADDRESS: U. S. DEPARTMENT OF ENERGY P. 0. BOX 398705 CINCINNATI, OHIO 45239
June 19, 1990
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TABLE OF CONTENTS
LIST OF APPENDICES . . . . . . . . . . . . . . . . . . . . . . . . . . . . i i
SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i i i
I . Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
I 1 . General Information . . . . . . . . . . . . . . . . . . . . . . . . 1 A . FMPC Location . . . . . . . . . . . . . . . . . . . . . . . . . 1 B . Radionuclide Emission Sources . . . . . . . . . . . . . . . . . . 1 C . General Meteorological Data . Cincinnati and Dayton . . . . . . 2 D .
Cincinnati Airport for CY-1989 . . . . . . . . . . . . . . . . 3 E . Urban/Rural Characteristics . . . . . . . . . . . . . . . . . . 3 F . Population . . . . . . . . . . . . . . . . . . . . . . . . . . 4
Meteorological Data . FMPC Meteorological Tower and Greater
I 1 1 . CY-1989 FMPC Uranium Air Emissions . . . . . . . . . . . . . . . . . 4 A . Monitored Dust Collectors . . . . . . . . . . . . . . . . . . . 5 B . Scrubber Emissions . . . . . . . . . . . . . . . . . . . . . . 5 C . Unmonitored Stack Emissions . . . . . . . . . . . . . . . . . . 5 D . Uranium Emissions from Building Exhausts . . . . . . . . . . . 6 E . Uranium Emissions from Laboratories . . . . . . . . . . . . . . 7 F . Uranium Emissions from Waste Pits . . . . . . . . . . . . . . . 7 G . Uranium Emissions from Non-Routine Events . . . . . . . . . . . 8
IV . CY-1989 FMPC Radionuclide Air Emissions . . . . . . . . . . . . . . 8 A . Radionuclide Emissions Estimation Method . . . . . . . . . . . 8
SolidSpill . . . . . . . . . . . . . . . . . . . . . . . . . . 9 C . Radionuclide Emissions Estimates . Plant 8 Sources . . . . . . 9 D . Radionuclide Emissions Estimates . Waste Pits . . . . . . . . . 10
B . Radionuclide Emissions Estimates . Monitored Stack Emissions, Unmonitored Stacks. Building Vents. Laboratories. and
E . Radionuclide Emissions Estimates . Uranium Metal Fines Fire . . 10
V . Radiological Impact Analysis for the FMPC . Calendar Year 1989 . . 10 A . Introduction . . . . . . . . . . . . . . . . . . . . . . . . . 10 B . Methods of Evaluation . . . . . . . . . . . . . . . . . . . . . . 10 C . Assumptions and Parameter Values . . . . . . . . . . . . . . . 1 1 D . Results o f the Dose Calculations . . . . . . . . . . . . . . . 1 1 E . Additional Calculations and Findings . . . . . . . . . . . . . 12
APPENDICES A . Figures B . Tables C . References D . Attachments
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1 4 4 2 LIST OF APPENDICES
APPENDIX A. FIGURES
F i g u r e 1 L o c a t i o n o f FMPC and V i c i n i t y F i g u r e 2 FMPC S i t e Overview F i g u r e 3 Locat ions of Maximal ly Exposed I n d i v i d u a l s F i g u r e 4 Wind Flow Pat te rns - C i n c i n n a t i and Dayton A i r p o r t s F i g u r e 5 FMPC S i t e S p e c i f i c Wind Flow P a t t e r n s
APPENDIX B. TABLES
Tab le 1 Table 2 Tab le 3 Tab le 4 Tab le 5 Tab le 6 Tab le 7 Tab le 8 Tab le 9
Tab le 10
Tab le 11
Tab le 12
Tab le 13
P o p u l a t i o n Est imates by Sec tor W i t h i n a F i f t y - M i l e Radius o f t h e FMPC P o p u l a t i o n Centers Within a F i v e - M i l e Radius o f t h e FMPC Summary o f CY-1989 FMPC S i t e A i r Emissions Phys ica l Parameters o f Representa t ive Sources A c t i v i t y o f Radionucl ides CY-1989 Moni tored Stacks Composite Sample A c t i v i t y o f Radionucl ides CY-1989 P l a n t 8 Composite Samples A c t i v i t y o f Radionucl ides Waste P i t s A c t i v i t y o f Radionucl ides Metal F ines F i r e C a l c u l a t e d Maximum I n d i v i d u a l Dose Equiva len ts (mrem) f rom Emissions o f Radionucl ides t o A i r Dur ing 1989 Maximum I n d i v i d u a l 50-Year Committed E f f e c t i v e Dose Equ iva len ts , With and Without Waste P i t s C a l c u l a t e d C o l l e c t i v e Dose Equiva len ts (person-rem) From Rout ine Emissions o f Radionucl ides t o A i r D y r i n g 1289 Atmospheric D ispers ion Fac tors (s/m x 10- ) f o r a Ground-Level and an Elevated Release Comparison o f 50-Year Committed E f f e c t i v e Dose E q u i v a l e n t s (mrem) a t A i r M o n i t o r i n g S t a t i o n s (AMS) Based on C a l c u l a t e d and Measured A i r Concentrat ions
APPENDIX C. REFERENCES
APPENDIX D. ATTACHMENTS
ATTACHMENT 1 Radionucl ide A i r Emission Source Compi la t ion ATTACHMENT 2 1989 Uranium Emissions I n v e n t o r y ATTACHMENT 3 Radionucl ide A i r Emissions by Groupings used For AIRDOS/DARTAB
Model i ng ATTACHMENT 4 A i r Emissions Annual Report Prov ided t o USEPA Headquarters by
DOE t o Demonstrate Compliance Wi th 40 CFR 61, Subpart H ATTACHMENT 5 Example Uranium Emissions C a l c u l a t i o n s ATTACHMENT 6 Example Rad ionuc l ide Emissions C a l c u l a t i o n s
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SUMMARY 4 ki 1 4 4 -
The purpose of this document is to provide supplemental information for the Annual Radionuclide Air Emission Report for Calendar Year (CY) 1989 for the Feed Materials Production Center (FMPC) located in Fernald, Ohio. The Annual Radionuclide Air Emission Report is provided to the United States Environmental Protection Agency for the purpose of demonstrating compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAP), 40 Code o f Federal Regulations (CFR) 61, Subpart H - National Emission Standard for Radionuclide Emissions From Department of Energy (DOE) Facilities. The supplemental information in this document consists of general descriptions of the FMPC and surrounding area, descriptions o f the methodologies used to estimate off-site dose to members of the public, and documentation of the methods and results.
New emission standards were promulgated by the EPA for radionucl ide emissions for DOE facilities on December 15, 1989. The (3-1989 dose estimates are still compared to the old standard o f 25 mrem whole-body and 75 mrem critical organ dose equivalent commitments in order to demonstrate compliance with 40 CFR 61, Subpart H for CY-1989. A l s o provided for informational purposes is a comparison to the new radionuclide standard, which will be applicable to future years (CY-1990 dose estimates forward). The new standard is 10 mrem effective dose equivalent. The Annual Radionuclide Air Emission Report demonstrates that the FMPC complies with the whole-body and critical organ dose standards, as well as demonstrates that the FMPC complies with the new effective dose equivalent standard, which will be applicable for future compliance demonstrations.
A comparison study is provided, which compares dose estimates at ambient air monitoring stations, as calculated by modeling o f estimated emissions from the FMPC and calculated from ambient measured radionuclide concentrations. Dose estimates based on modeling exceed dose estimates as calculated from ambient measured values, so that the modeling results are considered a conservative (higher than actual doses) estimate of off-site doses due to radionuclide emissions from the FMPC.
i i i 000804
.! r442 SUPPLEMENTAL INFORMATION FOR THE ANNUAL RADIONUCLIDE AIR EMISSION
REPORT FOR CALENDAR YEAR 1989 - NATIONAL EMISSION STANDARDS FOR HAZARDOUS A I R POLLUTANTS (NESHAP), 40 CFR 61, SUBPART H
FEED MATERIALS PRODUCTION CENTER
1. Introduction
The Feed Materials Production Center (FMPC) i s a federal f a c i l i t y f o r the production of highly pure uranium metal. The FMPC i s owned by the U.S. Department of Energy ( D O E ) w i t h program d i r ec t ion administered through the Oak Ridge Operations o f f i c e of the DOE.
The FMPC i s located in southwestern Ohio near t h e unincorporated v i l l age of Fernald in the Great Miami River Valley. The FMPC i s located about twenty miles (32.2 km), northwest of the City of Cincinnat i , Ohio and abou t two miles (3.2 km) southwest of Ross, Ohio (Figure 1 ) . The address of t he FMPC i s 7400 Willey Road, Fernald, Ohio 45030. The center of the s i t e i s located a t Lat i tude 39'-17'-56" and Longitude 84'-41'-16" (center of Plant 4 ) .
The primary a c t i v i t y of the Feed Materials Production Center (FMPC) i s the manufacture of purif ied uranium-metal products. The s i t e reprocesses uranium scrap metal and uranium t r iox ide (U03). Uranium hexafluoride (UF6) and uranium t e t r a f l u o r i d e (UF4) a re a l so handled and processed a t the FMPC. Radioactive mater ia l s handled and s tored a t the FMPC include pi tch blende ore residues containing radium stored i n the K-65 S i l o s , thorium and thorium compounds stored in several locat ions within the FMPC production a rea , uranium metal, uranium compounds, contaminated magnesium f luo r ide (MgFZ), and contaminated scrap metal.
11. General Information
A. FMPC Location
The FMPC, located i n southwestern Ohio, i s comprised of 1050 acres (425 hec ta re ) , approximately 850 acres (344 hectare) in northern Hamil ton County and 200 acres (81 hectare) i n adjacent But ler County (Figure 1 ) . The Production Area covers approximately 136 acres (55 hectare) in the center of t he FMPC (Figure 2) . The FMPC i s bounded by Ohio Route 126 t o the north, an e l e c t r i c a l transmission l i n e t o the e a s t , Willey Road t o the south, and Paddy's Run Road t o the west.
The topography of the region has been influenced by the Pleistocene g lac ia t ion . The FMPC is located in a two t o th ree mile (3.2 km t o 4 km) wide ancestral r i ve r va l ley known as the New Haven Trough. Today, the region i s influenced by flooding and meandering of the Great Miami River. The FMPC is located above the 500 year flood elevat ion f o r the region. A map of the plant and the area surrounding the FMPC i s included (Figure 3 ) . The FMPC s i t e topography i s a r e l a t i v e l y level e levated p la in , about 580 f e e t (177 meters) above sea l eve l . The land r i s e s s l i g h t l y t o the north, 699 f e e t (213 meters) e levat ion a t the northern boundary,and on the west slopes downward t o Paddy's Run, 551 f e e t (168 meters) .
B. Radionuclide Emission Sources
A l i s t i n g of the radionuclide emission sources a t the FMPC i s presented in Attachment 1. The 1 i s t i n g includes ex i s t ing radionuclide sources and some planned new equipment. The l i s t def ines the associated control equipment and FMPC emission
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? 1 4 4 q point for each source. The contribution from each emission p o i A t o the overa 1 FMPC uranium air emissions for CY-1989 is also presented- in the list. The radionuclide air emission source compilation forms the basis for the AIRDOS- EPA/DARTAB model runs to estimate doses from radiation exposures due to CY-1989 FMPC air emissions.
The approximate locations of the FMPC emission sources listed in Attachment 1 can be found by using Figure 2. The first number is the building number and the second number is the source number. For example, in the number 5-084, the building number is 5 and the source number is 084. Figure 2 has a listing of the site buildings and shows their respective locations.
C. General Meteorological Data - Cincinnati and Dayton Data from the Greater Cincinnati International Airport has been used to
characterize the climate of the region. The Greater Cincinnati International Airport meteorological data, in the past, has been more representative of the FMPC region than other data available. Additional wind flow data from the Dayton Airport is also included (Figure 4 ) .
The regional climate is defined as continental, with temperatures ranging from the average of 29.2'F (-1.56OC) in January to 7 5 . 7 O F (24.3OC) in July for the period 1960 through 1989. The highest temperature recorded from 1961 through 1989 was 103OF (39.4OC) in July, 1988, and the lowest was -25OF (-31.7OC) in January, 1977. The average days per year with a minimum temperature of 32OF ( O O F ) or less is 109 days and the average days with a maximum temperature of 90°F (32.2OC) or above is 20 days per year for the period 1962 through 1989. Frost depth ranges from 30 inches to 36 inches (76 to 91 cm).
During the winter and spring, frequent weather changes occur in southwestern Ohio as cyclonic storms pass from west to east over the area. In the summer, rainfall is produced by thunderstorms originating in the warm moist air which moves northward from the Gulf of Mexico along the Mississippi and Ohio River valleys. Fall is the season of minimum precipitation. Almost all snowfall occurs during the November through April period.
The average annual precipitation for the period 1960 through 1989 was 40.56 inches (103.0 cm) and ranged from 27.99 to 52.76 inches (71 to 134 cm) per year. The highest precipitation occurred during the spring and early summer. Precipitation was lowest in late summer and fall. The annual precipitation for 1989 was 49.61 inches (126.0 cm). The average annual snow fall for the same period was 23.5 inches (60 cm) with heaviest snowfall in January. Annual snowfall ranges from 6.5 to 53.9 inches (16.5 to 137 cm) per year. Snowfall during calendar year 1989 was 23.3 inches (59.2 cm).
Utilizing data from both the Cincinnati and Dayton airports, windflow data for the period 1948 through 1978 indicates that the prevailing winds were from the south-southwest (Figure 4). There is a greater component of wind direction from the west and north at Dayton than at the Cincinnati airport. Both data sources are very similar in terms of wind direction and wind speed (Figure 4 ) .
Average monthly wind speed for the Greater Cincinnati Airport ranged from 6.7 mph ( 3 . 0 m/sec) in August to 11.1 mph, (5.0 m/sec) in March for the period 1947 through 1989. Highest wind speeds occurred in winter and spring, while the summer and early fall had the lowest wind speeds. The maximum sustained wind speed (one
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minute or more) was 46 mph (20.6 m/sec) in January, 1976 and again in April, 1982. The strongest winds tend to come from the five wind directions in the west- northwest to south-southwest quadrants.
Ohio lies on the edge of the region of maximum tornado frequency. About 90 percent of the tornados which are observed in Ohio come from the west-southwest direction. One tornado touched the FMPC on May 10, 1969; however, no damage was reported. Another tornado passed near the northeast boundary of the FMPC on May 13, 1974 but caused no damage.
Heavy fog occurred an average of 24.5 days per year from 1963 through 1989. These days occur throughout the year with a maximum from September through November and a minimum from April through June.
D. Meteorological Data - FMPC Meteorological Tower and Greater Cincinnati Airport for CY-1989
A meteorological tower has been installed at the FMPC to provide site specific data. The meteorological tower, located southwest of the FMPC production area, began operat i ons i n mid- 1986. The FMPC meteorological tower measures meteorological data at the 10 meter level and at the 60 meter level. Data from the FMPC Meteorological Tower at the 10 meter level is used for the AIRDOS-EPA/DARTAB modeling of CY-1989 air emissions (Figure 5). The 10 meter level is closest to the height of FMPC emission points and is considered the most representative for modeling of air emissions from the FMPC for CY-1989. Data recovery for the FMPC meteorological tower at both the 10 meter and 60 meter levels was 95.7%. FMPC meteorological data is reviewed and verified by a meteorologist.
Temperatures recorded at the FMPC ranged from a low of -19.8'F (-28.8'C) on December 22, 1989 to a high of 92.1'F (33.4'C) on July 11, 1989. The average temperature at the FMPC for 1989 was 52.2'F (11.2'C). -
The average annual precipitation for 1989 from the Greater Cincinnati Airport was 49.61 inches (126.0 cm) and ranged from a low of 1.96 inches (4.98 cm) during December, 1989 to a maximum of 6.40 inches (16.26 cm) during March, 1989. The highest precipitation occurred during the spring and summer. Precipitation was lowest in the fall and winter months.
Prevailing winds at the FMPC, as measured at the 10 meter level at the FMPC Meteorological Tower were from the south-southwest (Figure 5). There are greater components of wind direction from the west-southwest, the southwest, the northeast, and the east northeast as measured at the 10 meter level at the FMPC than at the Greater Cincinnati Airport.
Windspeeds for 1989 averaged 4.4 mph (2.0 m/sec) at the 10 meter level and 7.2 mph (3.2 m/sec) at the 60 meter level. The maximum hourly wind speed recorded at the FMPC at the 10 meter level was 17.2 mph (7.7 m/sec) on January 3, 1989 and at the 60 meter level was 24.7 mph (11.0 m/sec) on September 23, 1989.
E. Urban/Rural Characteristics
The FMPC is located in both Hamilton and Butler Counties, parts o f which are urbanized. This area is characterized by residential, commercial, and light industrial development along the Great Miami River and highway corridors. The community of Ross lies at the junction of State Routes 126 and 128 about two miles
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northeast of the FMPC. Areas immediately surrounding the FMPC are primarily rural in nature, characterized by the predominance of agriculture, with some light industry and scattered residences.
Local land uses include gravel operations along the Great Miami River, industrial facilities, parks, and primary and secondary transportation corridors. Two commercial gravel extraction operations are located one mile (1.6 km) east and two miles (3.2 km) southeast of the FMPC.
One park that is used primarily during the summer lies in the vicinity of the FMPC. The Miami Whitewater Forest, located 5.0 miles (8.0 km) southwest of the FMPC, is one of the largest parks in Hamilton County.
Hamilton County does not have a county zoning plan. The majority of the FMPC is located within Crosby Township, which controls land use through zoning. Land immediately south of the FMPC is zoned industrial, and to the east is zoned agricultural. The FMPC existed prior to township zoning and is thus exempt from zoning ordinances.
F. Popul at i on
Most populated areas in the vicinity of the FMPC are unincorporated small towns and villages varying from an estimated population of 30 at Fernald to 3,000 at Ross. Table 1 identifies population by sector within a 50 mile (80 km) radius of the FMPC. Table 2 shows the populations of the towns within a five mile radius of the FMPC.
The population distribution in Table 1 was developed by Oak Ridge National Laboratory for the 1989 calendar year. The population distribution is estimated using 1980 raw census data and appropriate growth factors to arrive at the 1989 population distribution shown in Table 1.
The locations of the nearest residences to the FMPC were physically audited and verified during 1989. The distances and directions of residences developed from this audit were used in the AIRDOS/DARTAB modeling of off-site dose to determine the location of the maximally exposed off-site individual and to determine the estimated dose to the maximally exposed individual.
111. CY-1989 FMPC Uranium Air Emissions
An inventory of uranium air emissions from the FMPC was developed for CY-1989. Uranium is the primary radionuclide emission (in kilograms per year) to the air from the FMPC. Emissions were estimated for all identified emissions sources that were operated and/or emitted radionuclides to the air during CY-1989. This inventory includes emissions from stacks as well as fugitive dust emissions. The methods utilized for estimating air emissions from the FMPC are generally consistent with the methods used to develop emissions for "Addendum to FMPC-2082 History of FMPC Radionuclide Discharges", March, 1989. The methodology developed for the Addendum to FMPC-2082 is the summation of losses from monitored stacks, unmonitored stacks, building vents, fugitive sources and non-routine emissions. The uranium emissions and the sources of those emissions are listed in Attachment 1. Attachment 2 is a separate listing o f the CY-1989 uranium emissions inventory, which is grouped by method of emissions estimate and coincides with the description of the emissions methods listed below. Attachment 5 contains example uranium emissions calculations.
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A total of 30.1 kilograms (kgs) of uranium were estimated to be emitted to the air from the FMPC during CY-1989. This may be compared to estimated emissions to the air for CY-1988 o f 107.8 kgs o f uranium. The largest source of uranium emissions during CY-1988 was the U03 Gulping Scrubber, which had estimated emissions of 66 kg o f uranium. This scrubber was shut down and not operated during CY-1989. The second largest uranium emissions during 1988 were from Plant 8 Scrubbers, which had estimated emissions of 15.643 kg of uranium. For CY-1989 the Plant 8 Scrubbers emitted an estimated 3.751 kg of uranium. Another large source of uranium emissions during CY-1988 was the FMPC Waste Pit Area (Pits 4, 5, and 6) , which had estimated emissions of 13.25 kg of uranium. Waste Pit 4 was covered during CY-1988. Estimated fugitive dust emissions from Waste Pits 5 and 6 were the largest source of uranium emissions from the FMPC during CY-1989. Uranium emissions from the Waste Pits during CY-1989 are estimated to be 19.47 kg of uranium. An additional discussion of uranium emissions estimation methods is provided below.
A. Monitored Dust Collectors
Monitored stacks make up the greatest number of emission points that discharged uranium at the FMPC during CY-1989. Included in the CY-1989 inventory are 33 stacks, which had been in operation. The majority of the monitored stacks are exhausts from dust collectors. Collectively these sources accounted for about 2.6% of the losses for CY-1989. These emission points are monitored using continuous isokinetic particulate samplers. A sampler consists of a pleated paper filter in a cup-shaped holder. A portion of the discharge process stream is drawn through the filter leaving any particulate on the filter. At regular intervals, the filter elements are destructively analyzed for uranium. Emissions of uranium from the monitored emission point are then calculated by a formula that takes into consideration the stack volumetric flow rate and uranium concentration.
B. Scrubber Emissions
Two scrubber systems were in operation during calendar year 1989. These were the Rotary Kiln and the Primary Calciner, both located in Plant 8. Together these two sources accounted for about 12.5% of the losses for CY-1989. The method for determining losses is based on an emission factor for each emission point determined by testing of the emissions from the stack. The emission factor multiplied by the number of operating hours in the year gives the annual uranium emissions. A record of the actual operating hours is maintained.
C. Unmonitored Stack Emissions
Unmonitored stacks accounted for about 11.0% of the uranium losses recorded for CY-1989. Estimates of these rates were derived by either engineering calculation or actual stack emission measurements or a combination of both. In general, a detailed analysis was made of the processes transport mechanism, the characteristics of materials transported and the probable activity rates for each system. This information was utilized in the derivation of emission factors which, when used in conjunction with production per time period on a system-by-system basis, provided the input for a summary of emissions of unmonitored processes for C Y - 1989.
Included in this inventory are 15 sources which were operated during the year. .The majority o f the'se sources were operated on a limited basis and as a result were only small contributors to overall uranium losses to the air. In Plant 5 the
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Rockwell Air Cooling Wells, the Jolters and Breakout Jolter Muffler and the Remelt Furnace Oil Reclamation are all systems that were operated on a limited basis. With the exception of the Remelt Furnace Oil Reclamation, these systems are ventilated by air and emissions estimates have been completed by multiplying the number of derbies or pots handled times an emission factor. Contained in the emission factors are concentrations of uranium per pot or derby produced. For the Remel t Furnace Oi 1 Recl amat ion, concentrations of urani um have been determined by analysis of fugitive oil. Measured oil losses times this concentration provided the losses from this system.
Plant 6 has two sources identified as contributors to the annual emissions inventory. These are the Briquetting Scrubber and Scrap Pickling. For the Briquetting System, losses are determined by multiplying the volume of stack discharge times an emission factor. Derivation of this emission factor is based on measured concentrations of uranium in the exhaust streams per pound of uranium processed. For the Scrap Pickling system, losses are determined by multiplying the number of operating hours times an emission factor. The factor used was derived by the same methods as described above with the only difference being that the Briquetting system has a scrubber.
Four sources are included as being operative in Plant 8. They are the Drum Washer, Eimco Filters 1 & 2, and the Eimco Filter Hood Fan. Losses from the Drum Washer are determined by multiplying operating hours times an emission factor. This emission factor was established from operating stack data collected and analyzed for uranium concentrations. Emissions from the Eimco Filters are based on the gallons of water treated multiplied times the average concentration of uranium in the filtrate and a correction factor for the volume of water exiting the stack. For the Eimco Filter Hood Fan, losses are determined by multiplying the number of operating hours times the measured activity of the air in the building.
The only source recorded for Plant 9 is the Zirnlo Derby Pickle system. Losses from this system are determined by multiplying the number of derbies processed times an emission factor. The emission factor was determined from the results of EPA Method 5 stack testing.
Emissions from the Decontamination and Decommissioning (D&D) facilities are based on the number of batches processed multiplied by an emission factor. The emission factor was established using EPA Method 5 stack sampling data.
The final source contributor in this group is the Cooling Tower. Since various processes at the FMPC site use and recycle cooling water to the towers, this results in the contamination of the recirculating water. On returning to the tower the recirculating stream with its heat load is cascaded down over the tower fill, while air i s forced through the stream in the opposite direction. This air steam removes a certain amount of water in the form of mist along with the heat. Based on the water flow rate through the tower, the concentration of uranium in the recycle stream and the drift factor, the emission losses can be estimated for any given operating period. For the operating year CY-1989 the estimated losses from the cooling tower are one of the larger contributors to the overall uranium emissions inventory.
D. Uranium Emissions from Building Exhausts
Emission losses from building vents and exhausts make up about 1.7% of the Building ventilation emissions were calculated based losses reported for CY-1989.
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on data collected by continuous air monitors located in each plant. Continuous air monitors are located throughout the plants near processes suspected to produce radionuclide emissions. The monitors are used to measure alpha and beta radiation in microcuries per cubic centimeter. In order to convert from microcuries t o grams of uranium, the source of all radiation measured by the continuous air monitors was assumed to be normal uranium. This assumption is reasonable since the plants process large quantities o f depleted uranium and lesser amounts of slightly enriched uranium. Data on the uranium concentration in each plant for each month was averaged to provide an annual concentration for an operating year.
The total volumetric flow capacity of all the fans in each plant was determined from FMPC records or by estimation based on the size o f the exhaust fan. To calculate yearly emissions for each plant, the average annual concentration reported from the plant continuous air monitors was multiplied by the estimated hours each fan is operated per year and by 0.1 to account for dilution by building make-up air. The basis for the 0.1 dilution factor is that the concentration in the plants are only measured in the areas o f highest suspected concentration. The actual plant average uranium concentration in air is significantly lower than the average calculated from continuous air monitor results.
E. Uranium Emissions from Laboratories
Estimated emissions from the FMPC Laboratories constitute 6.3% of the total annual inventory for CY-1989. These estimates were based upon the average number of samples processed per year in each laboratory hood, the probable loss per sample and the estimated uranium concentration of the sample. The Laboratory emissions for CY-1989 are assumed equal to the annual uranium emissions estimate developed for the report "Addendum to FMPC-2082 History of FMPC Radionucl ide Discharges", March, 1989. This value is 1.9 kilograms of uranium per year.
F. Uranium Emissions from Waste Pits
By far the largest percentage of uranium air emissions estimated lost from the FMPC during CY-1989 are attributed to fugitive dust due to wind erosion at the FMPC waste pits. This has been calculated to be about 64.7% of the total annual estimated uranium emissions for CY-1989. The estimate is based on calculation using USEPA correlations for estimating fugitive dust losses from hazardous waste sites. Although this method is used for determining losses in and around storage piles, with minor changes it has been adapted for use in calculating losses from the waste pits. Basically the expected losses are equal to the exposed acreage multiplied times the number of days in storage times the uranium mass concentration times a factor. This factor is based on the silt and moisture content of the material, the number o f dry days during the year, and the amount of time that wind speed exceeds 12 miles per hour during the year.
Fugitive dust emissions from a given area can be considered to result from the fol1 owing activities:
- Load-in of materials into the area; - Wind erosion o f stored materials; - Vehicle movement in the area; and - Load-out of materials from the area.
For calculation of the fugitive dust emissions from the FMPC Waste Pits, only the second category listed above was judged to contribute significantly to the
7 000011
overall generation of fugitive dust emissions during CY-1989. Waste Pits 1, 2, 3, and 4 were covered during CY-1989 and emissions from these pits are zero. Only Waste Pits 5 and 6 were exposed during 1989. Wind erosion of the stored material in the exposed waste pits was estimated. There was no load-in to the waste pits during 1989, so load-in was considered not applicable. Vehicle movement in the actual area of the waste pits was minimal, so this term was considered not applicable. There was no load-out of material from the waste pits, so this category was considered not applicable.
The basic methodology used in determining the masses of contaminants (uranium) that potentially left the waste pits in CY-1989 was first to determine a factor for wind erosion of each waste pit. Once this emission factor was determined, the overall mass of particulate material that could become airborne was estimated. Finally, an average contamination concentration was applied to the overall mass of particulate emissions to estimate the mass of contaminant potentially leaving the waste pits.
Computations were performed in accordance with the method recommended by EPA in "Method for Estimating Fugitive Particulate Emissions from Hazardous Waste Sites", U.S. Environmental Protection Agency, Cincinnati, Ohio, August 1987,
G. Uranium Emissions from Non-Routine Events
EPA/600/2-87/066, PB87-232203.
Non-routine events are unusual events that are recorded either in an Unusual Occurrence Report (UOR) or a Minor Event Report (MER). During CY-1989 a total of 27 UORs and 163 MERs were recorded. Review of this record revealed that only two such events would qualify as contributors to the losses identified for the CY-1989 uranium emissions inventory. One event was a uranium metal fines fire that occurred June, 1989 in an overpacked drum. The metal fines fire occurred outside on the east side of Plant 6. The other event was a spill of material in a vehicle parking area southeast o f Plant 7. These two events account for 1.3% of the total uranium emissions inventory for CY-1989. Other events that may have lead to uranium emissions inside of buildings have not been included in this section. These are instead included in the uranium emissions from building exhausts section.
IV. CY-1989 FMPC Radionuclide Air Emissions
A. Radionuclide Emissions Estimation Method
Radionuclide release rates were calculated using radionuclide emission factors Radionuclide emission factors were determined per total mass of uranium released.
according to the following hierarchy:
1. Actual measurements during the most recent year available;
2. Weighted average emission factors based on data in FMPC 2082, "History of FMPC Radionuclide Discharges", May 1987; and/or
3. Assumptions based on knowledge of processes, age of materials, and equilibrium as appropriate.
The best available emission factors are then multiplied by the uranium emission rates to arrive at the radionuclide emission rate.
8 oo"ipo12
In order to model emissions by AIRDOS/DARTAB, the many emission sources at the FMPC were grouped into one or more representative emission points for each facility or area. Emission point selection was based on the EPA method for combining stacks in EPA-450/4-77-001: Guidelines for Air Quality Maintenance Planning and Analysis, Volume 10 (revised) - Procedures for Evaluating Air Quality .Impact of New Stationary Sources. The uranium emissions for each grouping were then multiplied by the appropriate radionuclide emission factors to obtain an estimate of radionuclide emissions from each emission grouping. The total radionuclide emissions for the FMPC site were then obtained by totaling the radionuclide emissions for all emission groupings. The total FMPC site emissions are listed in Table 3. The radionuclide emissions for the groupings modeled by AIRDOS/DARTAB are shown in Attachment 3. The physical parameters of the representative sources (the groupings in Attachment 3) used in the AIRDOS/DARTAB modeling is shown in Table 4.
The totals of the routine radionuclide em?ssions shown in Attachment 3 yield the radionuclide emissions shown in the Air Emissions Annual Report included as Attachment 4. The Air Emissions Annual Report was provided to USEPA Headquarters in Washington D.C. by the DOE prior to June 1, 1990 in order to demonstrate compliance with the National Emission Standards for Hazardous Air Pollutants for Radionuclides, 40 CFR 61, Subpart H. Example radionuclide emissions estimates are provided in Attachment 6.
B. Radionuclide Emissions Estimates - Monitored Stack Emissions, Unmonitored Stacks, Building Vents, Laboratories, and Solid Spill
Radionuclide emission factors in microcuries per kilogram of uranium (uCi/kg U) were developed from composite samples of filter analysis solutions for uranium from the FMPC monitored stacks. Several radionuclides were analyzed on a monthly basis with additional radionuclides analyzed on an annual basis. Additional radionuclide emission factors were estimated based on equilibrium or appropriate references. These uCi/kg U emission factors are shown in Table 5 along with the basis for development of the uCi/kg U value for each radionuclide. These emissions factors represent a weighted average emission rate of radionuclides from all of the monitored stacks at the FMPC. These emission factors were considered the best available for estimating off-site dose due to emissions from all monitored stack emissions, the unmonitored stack emissions with the exception o f Plant 8, building vents, laboratories, and the abnormal emissions from the solid spill that occurred during CY-1989.
C. Radionuclide Emissions Estimates - P l a n t 8 Sources
Radionuclide emission factors in microcuries per kilogram of uranium (uCi/kg U) were developed from composite samples of filter analysis solutions for uranium from the Plant 8 Scrubbers. The Plant 8 Primary Calciner and Plant 8 Rotary Kiln scrubber stacks were sampled extensively during CY-1989 for the purpose of refining the uranium emissions factors for these stacks. Several radionuclides were specifically determined for each test. Laboratory solutions from the sample analysis for these tests were composited for analysis for other radionuclides. Additional radionuclides were analyzed in the composite sample from all tests run in CY-1989 on the Primary Calciner and Rotary Kiln combined, since the same materials were processed in both Calciner and Kiln. Some radionuclide emission factors were estimated based on equil i brium or appropriate references. A separate set of radionuclide emission factors was developed for the Primary Calciner and Rotary Kiln scrubber stacks. A weighted average of these factors was applied to all other Plant 8 emissions. These uCi/kg U emission factors are shown in Table
9 000013
6 along with the basis for development of the uCi/kg U value for each radionuclide. These emissions factors represent a weighted average emission rate of radionuclides from the Primary Calciner and Rotary Kiln scrubber stacks. These emission factors are considered the best available for estimation of radionuclide emissions from all Plant 8 operations during CY-1989.
D. Radionuclide Emissions Estimates - Waste Pits Radionuclide emission factors in microcuries per kilogram of uranium
(uCi/kg U) were developed based on analysis of core samples of the Waste Pits. The Waste Pit core samples were taken for a Characterization Investigation Study. These uCi/kg U emission factors were developed for the CY-1988 emission inventory and were used without change for the CY-1989 emission inventory. Some radionuclide emission factors were estimated based on equilibrium or appropriate references. The uCi/kg U emission factors for the Waste Pits are shown in Table 7 along with the basis for development of the uCi/kg U value for each radionuclide. These emissions factors represent averages of the core samples for each waste pit and are considered the best available emission factors for estimation of radionuclide emissions from the Waste Pits.
E. Radionuclide Emissions Estimates - Uranium Metal Fines Fire
The uranium metal fines fire involved depleted uranium metal chips. Radionuclide emission factors were developed as follows. Uranium isotopes were estimated to be those typically found in depleted uranium. Other uCi/kg U values were taken from sampling results from the G5A-100 dust collector. The use of the values from the G5A-100 dust collector are considered a worst case estimate for the emissions estimate for the metal fines fire. Dust collector G5A-100 was selected as being representative of the metal fines fire radionuclide emissions, due to similar material being processed. The uCi/kg U emission factors for the metal fines fire are shown in Table 8 along with the basis for development of the uCi/kg U value for each radionuclide. These emissions factors are considered the best available for estimation of radionuclide emissions from the metal fines fire.
V. Radiological Impact Analysis for the FMPC - Calendar Year 1989 A. Introduction
Modeling of emissions to determine off-site dose due to radionuclide emissions from the FMPC was performed by the Oak Ridge National Laboratory (ORNL). Various input data for the modeling including the radionuclide emissions inventory, meteorological data, locations of residents, and stack data and parameters was developed and provided to ORNL by the Feed Materials Production Center. The results of the analysis of off-site dose completed by ORNL is presented below. The dose estimates discussed below are the same as those shown in the Air Emissions Annual Report included as Attachment 4. The Air Emissions Annual Report was provided to USEPA Headquarters in Washington D . C . by the DOE prior to June 1, 1990 in order to demonstrate compliance with the National Emission Standards for Hazardous Air Pollutants for Radionuclides, 40 CFR 61, Subpart H.
B. Methods o f Evaluation
Characterization of potential radiation doses due to radionuclides released to the atmosphere because of Feed Materials Production Center (FMPC) operations during 1989 was accomplished by calculating dose equivalents to nearby residents and to
10 000014
the entire population residing within 80 km of the plant. Doses were calculated using the Clean Air Act (CAA) suite of computer codes [Moore et al., 1979; Begovich et al., 1981; Dunning et al., 1980; Sjoreen and Miller, 19841, which was developed under EPA sponsorship for use in determining compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAP) - Radionuclides (CFR, 1986). The CAA package provides an integrated set of computer codes and data bases that simulate atmospheric and terrestrial transport of radionuclides released to the atmosphere and calculate resulting dose equivalents and health impacts. The atmospheric transport code, AIRDOS-EPA, calculates concentrations of released radionuclides in air, on the ground, and in foodstuffs (i.e., milk, meat, and vegetables). The code then calculates human exposures to and intakes of the radionucl ides in the various environmental media. Through the DARTAB computer code, the dose conversion factors (DCFs) in the RADRISK data base are applied to the calculated exposures and intakes of radionuclides to give estimates of individual and collective dose equivalents from inhalation o f and immersion in contaminated air, from exposure to contaminated ground surfaces, and from ingestion of locally grown foodstuffs (milk, meat, and vegetables).
Maximum individual dose equivalents were estimated as follows. First, the nearest residence to each facility (e.g., Plant 1) in each of the 16 major compass directions was located. (In some cases, more than one residence in a direction was chosen because a more distant residence for one facility was closer, perhaps in a different direction, for another facility.) Doses at each selected residence were calculated for each emitting facility. The highest total dose at a residence was then taken to be the dose received by the maximally exposed individual.
C. Assumptions and Parameter Values
The calculations were performed using meteorological data collected during 1989 at the 10-m level of the FMPC meteorological tower. The many facility-specific emission sources (stacks, vents, etc.) were analyzed and one or more representative sources were selected f o r each facility (see Table 4). Source selection was based on the EPA method for selecting one emission point to represent several [EPA, 19871. Radionuclide emission estimates for each representative source were provided by the FMPC. All nuclides were assumed to be in their least soluble form (to maximize doses via inhalation - the dominant pathway of exposure) and were assumed to have an AMAD of 1.0 micron.
A current estimate o f the population distribution within 80 km of the FMPC (Tables 1A and 1B) was obtained by extrapolation from 1980 census data. Beef, milk, and food crop production was assumed to be the maximum possible for the available ground area, an assumption that overstates these activities in the area. It was further assumed that one-third of the foodstuffs consumed by the local population was grown locally; the remaining two-thirds was assumed to be imported from outside the 80-km radius.
D. Results of the Dose Calculations
For routine emissions, the DARTAB computer code predicts the location of the maximally exposed off-site individual to be approximately 1150 m north o f the center of Plant 4, which we define as the center of the FMPC (Figure 3). This individual could have received a whole-body dose equivalent of 0.0037 mrem, a 50- year committed maximum organ (lung) dose equivalent of 34 mrem, and a 50-year committed effective dose equivalent of 5.2 mrem (Table 9). These dose equivalents are well below the old NESHAP limits, 25 mrem to whole body and 75 mrem to any
11
organ, and the new limit, 10 mrem effective. Approximately 93% of the maximally exposed individual's doses are attributable to emissions from the waste pits (see Table 10). If waste-pit emissions are excluded, the maximally exposed individual is predicted to be approximately 1030 m east-southeast of the plant center and could receive a 50-year committed effective dose equivalent of.1.2 mrem (Figure 3). This individual's dose is due primarily to emissions from the Laboratory Building (65%) and Plant 8 (22%).
Two non-routine emission scenarios also were evaluated (Table 9). One scenario consisted of a uranium fire of short duration, during which the wind blew only toward the south. The second scenario involved a long-term exposure to material spilled on the ground; annual-average meteorological conditions were used in the calculations. The maximally exposed individual for the fire was found to reside approximately 1260 m south of the fire and could have received a whole-body dose equivalent of 0.000022 mrem, a 50-year committed maximum organ (lung) dose o f 0.57 'mrem, and a 50-year committed effective dose equivalent of 0.069 mrem. The maximally exposed individual for the spill was found to reside approximately 1150 m north of the spill and could have received a whole-body dose equivalent of 0.000000068 mrem, a 50-year committed maximum organ (1 ung) dose equivalent of 0.00083 mrem, and a 50-year committed effective dose equivalent o f 0.00010 mrem.
The calculated collective 50-year committed effective dose equivalent to the 2.643 million persons residing within 80 km (50 mi) of the FMPC is 63 person-rem (see Table 11). Collective whole-body and organ dose equivalents also are given in Table 11.
Details of the parameter vaiues, air concentrations and deposition rates, and dose distributions are listed in the computer printouts.
E. Additional Calculations and Findings
To demonstrate that air concentrations of emitted nuclides and subsequent dose estimates decrease with distance from the emission source, atmospheric dispersion factors (X/Q values) for a ground-level release (the waste pits) and an elevated release (the Cooling Towers) are presented in Table 12. Only factors for the prevailing wind directions are listed. The printouts contain values for all 16 compass directions.
Radionuclide concentrations, 50-year commi tted maximum organ (lung) dose, and 50-year committed effective dose equivalents at the seven perimeter air monitoring stations and seven of the nine other stations (see Figure 3) were calculated using emissions data. These calculations were adjusted to simulate the absence of the waste pits. Dose equivalents at all the air monitoring stations were calculated a1 so by substituting measured radionuclide concentrations for the calculated ones in AIRDOS-EPA and DARTAB. Table 13 contains the resulting dose equivalents. Note that calculated doses with the waste pit contribution included are much higher than the measured values. Removing the waste-pit contribution results in very good agreement between doses based on emissions data and measured concentrations. Since measured concentrations contain naturally occurring radionucl ides, one would expect doses based on such concentrations to be higher than doses based on emissions only. The disparity between doses calculated with the waste pit emissions included and doses based on measured concentrations suggest that waste pit emissions may be greatly overestimated.
12
APPENDICES
A . Figures
6. Tables
C . References
0. Attachments
006301'7
APPENDIX A
FIGURES
Figure 1. Location of FMPC and Vicinity I
000019
Figure 2. FMPC Site Overview
(;;;) BUILDING IDENTIFICATION Building Grid Building Grid LD. NO. Coordinates rille I.D. No. Coordmales rille
00 l a l b 2a 2b 2c 2d 2e 3a 3b 3c 3d 3e 3f 39 3h 4a 4b 4c 5 6 7 8a 8b
1 Oa 10b 11 12a 12b 12c 13a 13b 13c 14 15 16 18a 18b 18c 18d 18e 18f 189 19a 19b 20a 20b 20c 20d 20e 2of 209 20h 20j 22a 22b 22c 23
I 9
.t
c-3 c-3 8-3 8-3 8-3 c-3 c-3 8-3 8-3 8-3 8-3 6-3 8-3 8-3 8-3 8-4 8-4 8-4 8-4 B-5 6-4 8-3 8-3 c-5 0-4 0-4 A-4 c-4 c-4 C-4 A-3 A-3 A-3 A-4 A-3 A-5 c-2 8-3 c-4 6-3
D-1 c-1 c-4 A-3 c-4 0-4 C-4 6-5 8-3 6-3 A-3 0-4 8-2 6-5 A-3 A-5
t
t
General Preparation Plant Plant 1 Storage Building Ore Refinery Plant Lime Handling Building Bulk Lime Handling Building Metal Dissolver Building NFS Storage and Pump House Maintenance Building Ozone Building Control House NAR Towers Hot Raffinate Building Digestion Fume Recovery Refrigeration Building Refinery Sump Green Salt Plant Plant 4 Warehouse Plant 4 Maintenance Building Metals Production Plant Metals Fabricating Plant Plant 7 Recovery Plant Maintenance Building Special Products Plant Boiler Plant Boiler House Maintenance Building Service Building Maintenance Building (Main) Cylinder Storage Building Lumber Storage Building Pilot Plant Wet Side Pilot Plant Maintenance Building Sump Pump House Administration Building Laboratories Main Electrical Substation Surge Lagoon General Sump Coal Pile Runoff Basin Biodenitrification Towers Storm Water Retention Basin Pit 5 Sluice Gate Clearwell Pump House Metal Tank Farm Pilot Plant Ammonia Tank Farm Valve/Con t rol Bu i Id i ng Filter/Chemical Building Cooling Towers Elevated Storage Tank (Potable HzO) Well House Well House Well House Process Water Storage Tank Lime Slurry Pits Gas Meter Building Storm Sewer Lift Station Truck Scale Meteorological Tower
24a 24b 25a 25b 25c 25d 25e 26a 26b 28a 28b 30a 30b 31 32 34a 34b 35a 35b 37 38 39a 39b 39c 44a 44b 44c 44d 44e 45 46 51 53a 53b 54a 54b 55a 55b 56 60 61 62 63 64 65 66 67 68 69 71 72 73 77 78 79 80 81 82
0-3 c-4
t
A-5
8-3 8-3 A-4 A-4 c-3 c-3 A-5 D-5 6-1 8-1 c-1 8-1 A-3 0-4 8-3 8-3 B-3 A-5 A-4 A-3 A-3 A-4 8-3 A-5 A-2 A-4 A-4 A-3 A-3 8-4 8-4 D-3 D-3 D-3 0-3 D-4 D-5 0-5 c-3 c-3 A-3 D-5 c-3 c-3
c-5
B-5 8-3 c-5 B-5
t
Railroad Scale House Railroad Engine Building Chlorination House MH #175 Sewage Lift Station Building U.V. Disinfection Building Digester Control House Pump House - H.P. Fire Protection Fire Protection Storage Tank Security Building Human Resources Building Chemical Warehouse Drum Storage Warehouse Engine House - Garage Magnesium Storage K-65 Storage Tank - North K-65 Storage Tank - South Metal Oxide Storage Tank - North Metal Oxide Storage Tank - South Pilot Plant Annex Propane Storage Incinerator Building Warehouse Incinerator Bulding Sprinkler Riser House Trailer Complex - 6-Plex - East Trailer Complex - 3-Plex Trailer Complex - 7-Plex - South Trailer Complex - 7-Plex - North Trailer Complex - 10-Plex Building 45 Heavy Equipment Garage UFS to UF4 Reduction Facility I I Health, Safety & Production Control Building In-Vivo Building UFS to UF4 Reduction Facility I WarehouseMleather Shelter Slag Recycling Plant Slag Recycling Pit/Elevator CP Storage Warehouse Quonset Number 1 Ouonset Number 2 Quonset Number 3 KC-2 Warehouse Plant 9 Warehouse Plant 5 Warehouse Drum Reconditioning Building Plant 1 Storage Building Pilot Plant Warehouse Decontamination Building General In-Process Storage Warehouse Drum Storage Building Fire Brigade Training Center Building Finished Products Warehouse New D&D Facility (On Hold) Plant 6 Warehouse Plant 8 Warehouse Plant 9 Warehouse Receivina & lncomino Materials Inspection Area
Outside of perimeter Securitv Fence . "NOTE: Any-Unidentified Area is Referr& to as 00 General
Page 2 0063088)
~
WMCO Graphics XI136
0 114 112 1 2
SCALE OF MILES
LEGEND
Maximally Exposed Individual - Heavy Duty Roads -%- FMPC Boundary
Maximally Exposed Individual
@ (Including Waste Pit Emissions)
@ (Excluding Waste Pit Emissions)
- Medium Duty Roads
- Light Duty Roads
@-Fixed Air Monitoring Stations
-
000821 Figure 3. Locations of Maximally Exposed Individuals
60
3
Wind Rose for the FMPC, 1989, Meters Showing Direction from which the Wind
-Percent of Time
Blows.
Wind Rose for the FMPC, 1989, 10 Meters Showing Direction from which the Wind Blows.
Figure 5 . FMPC Site Specific Wind Flow Patterns
00023
APPENDIX B
TABLES
000024
TABLE 1
POPULATION ESTIMATES BY SECTOR
OF THE FMPC WITHIN A F IFTY-MILE RADIUS
TABLE 1A. INCREMENTAL POPULATION DISTRIBUTION AROUND THE FMPC FOR 1989 Distance,
m i 1 es 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 N 7 64 77 108 125 1008 16676 7161 16737 12369
NNE 5 57 65 1 1 1 300 13702 -7595 8288 31333 78291 NE 8 206 120 129 317
ENE 16 106 2714 5 47 E 24 62 119 89 235
ESE 16 68 137 206 292 SE 8 69 107 153 192
SSE 15 67 88 256 591 S 8 69 97 384 620
ssw 9 77 154 290 354 sw 9 85 143 129 130
wsw 17 84 142 216 296 W 9 79 135 215 270
WNW 8 66 102 161 213 NW 12 63 99 154 219
38550 31258 34442 38965 52064 20714 8376 4814 1171 7081 2488 1596 1091
45545 17295. 53951 160794 273363 218659 32804 9492 15147 3749 3650 4242 1398
96440 3 1720 39591 72536 94394 55517 34309 7718 10752 7092 10355 6469 3222
189514 13520 17675 24073 26815 931 1 9475 6022 3708 7243 5805 4255 26366
317133 25702 10403 13277 15853 8685 9575 9695 4916 5908 16385 12060 9417
NNW 17 64 102 186 316 1538 12963 4921 48181 13725 TOTAL 188 1286 4401 2792 4517 258858 877323 490485 440033 563394
TABLE 1B. CUMULATIVE POPULATION DISTRIBUTION AROUND THE FMPC FOR 1989 Distance, mi 1 es 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50
N 7 71 148 256 381 1389 18065 25226 41963 54332 NNE
NE ENE
E ESE
SE SSE
S ssw sw
wsw W
WNW
5 62 127 238 538 8 214 334 463 780 16 122 2836 2841 2888 24 86 205 294 529 16 84 221 427 719 8 77 184 337 529 15 82 170 426 1017 8 77 174 558 1178 9 86 240' 530 884 9 94 237 366 496 17 101 243 459 755 9 88 223 438 708 8 74 176 337 550
14240 39330 34146 3497 1 39684 52593 21731 9554 5698 1667 7836 3196 2146
21835 84875 51441 88922 200478 325956 240390 42358 15190 16814 11585 6846 6388
30123 181315 83161 128513 273014 420350 295907 76667 22908 27566 18677 17201 12857
61456 370829 96681 146188 297087 447165 305218 86142 28930 3 1274 25290 23006 17112
139747 687962 122383 156591 3 10364 463018 313903 957 17 38625 36 190 31828 39391 291 72
NW 12 75 174 328 547 1638 3036 6258 32624 42041 NNW 17 81 183 369 685 2223 15186 20107 68288 82013
TOTAL 188 1474 5875 8667 13184 272042 1149365 1639850 2079883 2643277
000825
1 4 4 2
TABLE 2
POPULATION CENTERS WITHIN A F IVE-MILE RADIUS OF THE FMPC
POPULATION APPROXIMATE ESTIMATED CENTER D I STANCE POPULATION
Fernal d 1.75 30
Shandon 2.0 200
Venice (Ross)
New Bal t i more
New Haven
Dun1 ap
2.5
2.75
3.0
4.0
3,000
200
200
100
H a r r i s o n 5.0 4.408
T o t a l 8,138
TABLE 3 b- / 4 4 2 5--
SUMMARY OF CY-1989 FMPC SITE A I R EMISSIONS
ROUTINE EMISSIONS
RADIONUCLIDE (Ci/vr 1
U-234 4.95 x 10-3 U-235 5.72 x 10-4 U-236 4.26 x 10-4 U-238 9.89 x 10-3 Sr-90 1.48 x 10-5 Tc-99 8.70 x 10-4 Ru-106 7.01 x 10-5 CS- 137 4.92 x 10-5 Ba-137111 4.92 x 10-5 Ra-226 1.93 x 10-4 Ra-228 2.93 x 10-5 Th-228 8.67 x 10-5 Th-230 3.62 x 10-3 Th-232 3.27 x 10-5 Th-234 1.62 x 10-2 Pa-234m 1.62 x 10-2 Np-237 5.89 x 10-6 PU - 238 2.40 x 10-6 Pu-239 1.43 x 10-5 Pu-240 5.52 x 10-6 Pu-241 6.17 x 10-5 PU - 242 2.58 x 10-9
TOTAL EMISSIONS INCLUDING ABNORMAL CIRCUMSTANCES (Ci /yr 1
5.02 x 10-3 5.74 x 10-4 4.26 x 10-4 1.00 x 10-2 1.48 x 10-5 8.76 x 10-4 7.16 x 10-5 5.04 x 10-5 5.04 x 10-5 1.93 x 10-4 2.93 x 10-5 9.02 x 10-5 3.62 x 10-3 3.36 x 10-5 1.73 x 10-2 1.67 x 10-2 6.02 x 10-6 2.42 x 10-6 1.43 x 10-5 5.53 x 10-6 6.17 x 10-5 2.58 x 10-9
TABLE 4
PHYSICAL PARAMETERS OF REPRESENTATIVE SOURCES
Faci 1 i t y Release From Re1 ease Diameter Gas ex i t
Plant 1 Oust Collectors 20.4 0.25 11.2 Building Vents 19.6 1.3 11.4
Heiqht, m m Velocity. m/s
Plant 213 Dust Collectors 20.4 0.41 16.4 Building Vents 16.7 1.3 11.4
Plant 4 Oust Collectors 29.6 0.61 6.8 Building Vents 29.9 1.2 11.4
Plant 5 Dust Collectors 17.4 0.56 9.6 Process 17.4 0.73 14.9 Building Vents 17.1 1.3 11.4
Plant 6 Dust Coll ec to r s 7.6 1.2 11.2 Process 17.4 0.46 17.8 Building Vents 13.2 1.3 11.4
Plant 8 Dust Col 1 ec to r s 13.7 0.71 7.9 Process 13.7 0.31 4.3 Building Vents 15.6 1 .o 11.4
Plant 9 Process 12.5 0.36 8.8 Building Vents 13.2 1 .o 11.4
* Plant 69 D&D 6.9 0.81 14.6
Cooling Tower 14.9 6.2 7.2
Laboratory Bldg. 615-001 3.4 0.31 7.5 Fume Hoods (1) 5.3 0.30 7.5
P i l o t Plant Dust Coll ec to r s 9.1 0.86 3.6
Waste Pits 1 .o 162.4 0.0
1) The fume hood s tack physical parameters a r e a typ ica l s tack.
000028
TABLE 5
ACTIVITY OF RADIONUCLIDES CY-1989 MONITORED STACKS COMPOSITE SAMPLE
MICROCURIES PER RADIONUCLIDE SOLUBILITY KILOGRAM URANIUM
U-234 (1) Y 298.6 U-235 (1) Y 15.8 U-236 (1) Y 11.6 U-238 (1) Y 333.6 Sr-90 (2) Y 1.76 Tc-99 (3 ) W 36.94 RU-106 (3) Y 6.86 CS-137 (2) D < 5.13 Ba-137m (4) D < 5.13
Ra-228 (2 ) Y < 0.85 Th-228 (2) Y 8.97 Th-230 (2) Y 26.94 Th-232 (2) Y 1.41 Th-234 (1 ) Y 1319. Pa-234m (5) Y 1319. Np-237 (2 ) Y 0.107 PU-238 (2) Y 0.127 PU-239 (2) Y 0.839 PU-240 (2) , Y 0.214 PU-241 (2) Y 3.125 PU-242 (2 ) Y 0.0000466
Ra-226 (2) Y 0.212
(1) Mass weighted average o f month ly composite samples analyzed a t t h e FMPC. (2) Annual composi te sample analyzed by an o f f s i t e c o n t r a c t o r . (3) From Table 5 o f " D r a f t Assessment o f R a d i a t i o n Dose and Cancer R i s k f o r
Emissions f rom 1951 t h r o u g h 1984", prepared by I T Corpora t ion , March, 1989. (4) Assumed i n e q u i l i b r i u m w i t h Cs-137 w i t h t h e same a c t i v i t y va lue. (5) Assumed i n e q u i l i b r i u m w i t h Th-234 w i t h t h e same a c t i v i t y va lue. (6) For emissions c a l c u l a t i o n s " l e s s - t h a n " va lues are considered t o be ''equal -
to ' ' values.
000029
TABLE 6
ACTIVITY OF RADIONUCLIDES CY-1989 PLANT 8 COMPOSITE SAMPLES
ROTARY KILN CALCINER MICROCURIES PER MICROCURIES PER
RADIONUCLIDE SOLUBILITY KILOGRAM URANIUM KILOGRAM URANIUM
U-234 (1) Y 437.3 392.2 U-235 (1) Y 20.1 19.2 U-236 (1) Y 27.2 25.0 U-238 (1) Y 332.8 332.9 Sr -90 ( 2 ) Y 0.0951 0.0951 Tc-99 (3) W 36.94 36.94 Ru-106 (3) Y 6.86 6.86 CS-137 (2 ) D 0.5 0.5 Ea-137m ( 4 ) D 0.5 0.5 Ra-226 (2 ) Y 0.00979 0.00979 Ra-228 (2 ) Y < 0.028 < 0.028 Th-228 (2 ) Y 0.0268 0.0268 Th-230 (2 ) Y 0.815 0.815 Th-232 (2) Y 0.016 0.016 Th-234 (1 ) Y 1027.4 276.1 Pa-234111 (5 ) Y 1027.4 276.1 Np-237 (2 ) Y 0.185 0.185 Pu-238 (2) Y 0.156 0.156 Pu-239 (2 ) Y 1.637 1.637 Pu-240 (2) Y 0.424 0.424 Pu-241 (2) Y 6.295 6.295 Pu-242 (2 ) Y 0.0000861 0.0000861
C a l c i n e r 1989 composi te sample and t h e Rotary K i l n 1989 composite sample were analyzed separa te l y a t t h e FMPC. The Rotary K i l n and Ca lc ine r composite samples were combined and analyzed by an o f f s i t e c o n t r a c t o r f o r these rad ionuc l ides. From Table 5 o f " D r a f t Assessment o f Rad ia t i on Dose and Cancer R isk f o r Emissions f rom 1951 through 1984", prepared by I T Corporat ion, March, 1989. Assumed i n e q u i l i b r i u m w i t h Cs-137 w i t h t h e same a c t i v i t y va lue. Assumed i n e q u i l i b r i u m w i t h Th-234 w i t h t h e same a c t i v i t y va lue. For emissions c a l c u l a t i o n s " l ess - than" va lues are considered t o be ''equal - t o " Val ues. For r a d i o n u c l i d e emissions es t imates f o r P l a n t 8 emissions o t h e r than t h e C a l c i n e r and Rotary K i l n , weighted averages o f t h e emissions f a c t o r s f o r t h e C a l c i n e r and Rotary K i l n were used. The weighted averages were determined by t h e f o l l o w i n g formula. { [ (uranium f rom c a l c i n e r kg /y r ) ( rad ionuc l i d e emission f a c t o r uCi/kg U ) ] t [ (uranium f rom k i l n k g / y r ) ( r a d i o n u c l i d e emission f a c t o r uCi/kg U) ] ) / ( t o t a l uranium from t h e k i l n and c a l c i n e r )
000030
TABLE 7
A C T I V I T Y OF RADIO WASTE P I T !
RADIONUCLIDE SOLUBILITY U-234 (1) Y U-235 (1) Y U-236 (2 ) Y U-238 (1) Y Sr -90 (1) Y Tc-99 (1) W RU-106 (1) Y CS-137 (1) D Ba-137m (3) D Ra-226 (1) Y Ra-228 ( 4 ) Y Th-228 (1) Y Th-230 (1 ) Y Th-232 (1) Y Th-234 (6) Y Pa-234m (6) Y Np-237 (1) Y PU-238 (1) Y PU-239 (1) (5) Y PU-240 (1) (5) Y PU-241 (7) Y
WASTE P I T 5 MICROCURIES PE KILOGRAM URANl
331.8 17.8 12.9
333.3
662.5 ND
4.15
< 13.5 < 13.5
287.2 35.4 45.6
35.4 333.3 333.3
5135
5.31 1.04 1.3 1.3 8.8
20.4 12.9
332.9 0.037 2.49
0.34 0.34
0.01 0.0186 0.52 0.01
ND
ND
332.9 332.9
0.049 0.015 0.085 0.085 0.58
Rad ionuc l ide Emission Fac tors f o r 1988 were developed as descr ibed below f o r t h e waste p i t s . The same values were used f o r 1989.
Values a r e averages o f c o r e sample analyses performed on each waste p i t . The s p e c i f i c analyses a r e l i s t e d i n t h e f o l l o w i n g document; Solow, A. J. and Phoenix, D. R., " C h a r a c t e r i z a t i o n I n v e s t i g a t i o n Study, Vol . 2: Chemical and R a d i o l o g i c a l Analyses o f t h e Waste Storage P i t s " , November 1987, FMPC/SUB 008, Vol . 2 UC-70, Appendix D. U-236 va lues a r e assumed equal t o t h e s i t e average f o r FMPC processes as analyzed f o r composite d u s t c o l l e c t o r f i l t e r samples f o r 1988. Ba-137m i s assumed t o be i n e q u i l i b r i u m w i t h Cs-137, i . e . Ba-137m a c t i v i t y equals t h a t o f Cs-137. Ra-228 i s assumed t o be i n e q u i l i b r i u m w i t h Th-232, i .e . Ra-228 a c t i v i t y equals t h a t o f Th-232. Pu-239/240 - h a l f of t h e analyzed va lues d iscussed i n 1 above are p r o p o r t i o n e d t o each. Th-234 and Pa-234m a r e assumed t o be i n e q u i l i b r i u m w i t h U-238, i . e . t h e Th- 234 and Pa-234m a c t i v i t i e s a r e equal t o t h a t o f U-238. Pu-241 i s assumed t o be i n t h e same r a t i o t o Pu-239/240 as i s seen f o r FMPC processes as analyzed f o r composi te d u s t c o l l e c t o r f i l t e r samples f o r 1988. 'For emissions c a l c u l a t i o n s " l e s s - t h a n " va lues a r e considered t o be "equal - t o " va lues.
4 L: ? 4 4 2 TABLE 8
ACTIVITY OF RADIONUCLIDES METAL FINES FIRE
MICROCURIES PER RADIONUCLIDE SOLUBILITY KILOGRAM URANIUM
U-234 (1) U-235 (1) U-236 (1) U-238 (1)
Tc-99 (2) Ru-106 (2) CS-137 (2)
Sr-90 (2)
Ba-137m (2) Ra-226 (2) Ra-228 (2) Th-228 (2) Th-230 (2) Th-232 (2) Th-234 (2)
Np-237 (2) Pu-238 (2) Pu-239 (2)(3) Pu-240 (2)(3)
Pa-234m (2)
Y Y Y Y Y W Y D D Y Y Y Y Y Y Y y Y Y Y
186. 4.41 0.637
334. < 0.19 17.
< 3.9 3.1 3.1 0.058 0.12 9.3 2.7 2.3
2900. 1300.
0.33 0.062 0.136 0.034
(1) Theoretical isotopic values for depleted uranium. (2) (3)
(4)
Values from sampling results o f G5A-100 dust collector. Combined Pu-239/240 value from sampling results o f G5A-100 dust collector. Pu-239 and Pu-240 are assumed to be in the same proportion as analyzed in the 1988 dust collector composite sampler. Recycle material i s not used, so Pu-241 i s assumed equal to zero.
000832
TABLE 9
CALCULATED MAXIMUM INDIVIDUAL DOSE EQUIVALENTS (mrem) FROM EMISSIONS OF RADIONUCLIDES
TO AIR DURING 1989
Emi s s i on Who1 ea Effect i veb Endosteumb Lungb Redb L i verb Source Body Marrow
Rout i nec 0.0037 5.2 27. 34 2.2 0.1
U Fired 0.000022 0.069 0.023 0.57
SDillC 0.000000068 0,00010 0.0001 1 0.00083
a Due to external irradiation and intake o f 137Cs.
Fifty-year committed dose equivalents.
Individ.ua1 resides approximately 1150 rn north of the plant center.
Individual resides approximately 1260 m south o f the plant center.
000033
TABLE 10
MAXIMUM INDIVIDUAL 50-YEAR COMMITTED EFFECTIVE DOSE EQUIVALENTS, WITH AND WITHOUT WASTE P I T S
Faci 1 i t y W i t h Pitsa Without Pits’ (mrem) ( X I (mrem) (%I
Plant 1 0.0059 0.11 0.0035 0.3
Plant 2/3 0.0024 0.05 0.0030 0.2
Plant 4 0.0097 0.19 0.013 1.1
Plant 5 0.0073 0.14 0.017 1.4
Plant 6
Plant 8
0.027 0.51
0.095 1.83
0.056 4.6
0,26 21.8
Plant 9 0.0084 0.16 0.024 2.0
Plant 69 0.00041 0.01 0.00077 0.1
Cool i ng Trjwer 0.023 0.44 0.039 3.2
Laboratory Bu i 1 d i ng 0.21 4.05 0.78 64.8
P i l o t Plant 0.0011 0.02 0.0038 0.3
Waste P i t s 4.8 92.51
Total 5.2 100. 1.2 100.
a Maximally exposed individual res ides 1150 m north of the p lan t cen ter .
Maximally exposed individual r e s ides 1030 m eas t - southeas t of the plant center .
TABLE 11
CALCULATED COLLECTIVE DOSE EQUIVALENTS (person-rem) FROM ROUTINE EMISSIONS
OF RADIONUCLIDES TO A I R DURING 198ga
Who1 eb Effective' Endos teum' Lung' Red' L i ver' Bodv Marrow
0.051 63 2 50 440 20 0.98 ~~ ~
a Total population is approximately 2.643 million persons.
Due to external irradiation and intake of 137Cs.
' Fi fty-year committed dose equi Val ents.
000035
TABLE 12
ATMOSPHERIC DISPERSION FACTORS
AND AN ELEVATED RELEASE (s/rn3 x io-6) FOR A GROUND-LEVEL
Ground-1 eve1 Re1 ease E l evated Re1 ease Dis tance, m F a c t o r Dis tance, m F a c t o r
660 6.9 1210 1.02
800 4.8 1350 0.97
930 3.6 1440 0.93
1070 2.8 1580 0.88
1230 2 . 2 1680 0.84
1350 1.9 1750 0.81
1670 1.3 1850 0.77
1890 1 .o 2070 0.70
2100 0.9 2190 0.66
TABLE 13
COMPARISON OF 50-YEAR COMMITTED EFFECTIVE DOSE EQUIVALENTS (mrem) AT AIR MONITORING STATIONS (AMS) BASED ON CALCULATED AND MEASURED A I R CONCENTRATIONS
E f f e c t i v e Dose Eau iva len ts Lunq Dose Cal c u l a ted Cal c u l a ted
- AMS Waste P i t s Measured Waste P i t s Waste P i t s Measured Waste P i t s C a l c u l a t e d No Cal c u l a t e d No
1
2
3
4
5
6
7
8
9
10
11
12
13
6.9
3.0
4.3
1.6
1.1
2.2
1.3
5.3
8.1
0.29
0.20
0.069
0.52
0.33
0.40
0.68
0.27
0.24
0.40
0.27
0.61
1.6
0.23
0.15
0.14
0.14
0.44
0.69
1.7
0.73
0.57
0.63
0.23
1.3
1.9
0.15
0.091
0.026
0.21
45.3
20.3
30.3
11.1
8.3
15.0
8.5
36.5
55.4
2.1
1.5
0.5
3.7
2.5
3.2
5.4
2.0
1.8
3.1
2.1
4.6
13.2
1.8
1.2
1.1
1.1
3.6
5.6
13.9
5.3
4.6
5.1
1.8
10.6
15.3
1.2
0.7
0.2
1.7
14 0.50 0.15 0.21 3.5 1.2 1.7
15 0.28 2.2
16 0.30 2.3
0 0 0 03’7
APPENDIX C
REFERENCES
REFERENCES
1. O'Donnell , J. P. Witherspoon, and S . J. C o t t e r , " C h a r a c t e r i z a t i o n o f P o t e n t i a l R a d i o l o g i c a l Consequences f rom Radionucl i d e s Re1 eased t o t h e Atmosphere f rom Opera t ions a t t h e Feed M a t e r i a l s Produc t ion Center" , Oak Ridge N a t i o n a l Labora tory , May 23, 1990.
2. C. L. Begovich e t a l . , 1981. DARTAB: A Proqram t o Combine A i r b o r n e Rad ionuc l ide Exposure Data w i t h Dos imet r ic and H e a l t h E f f e c t s Data t o Generate T a b u l a t i o n s o f P r e d i c t e d H e a l t h Impacts, ORNL-5692, Oak Ridge N a t i o n a l Laboratory , Oak Ridge, TN.
3. CFR, 1980. Code o f Federal Regulat ions, T i t l e 40, P a r t 61, U.S . Government P r i n t i n g O f f i c e , Washington, D.C.
4. D. E . Dunning, Jr., R. W . Legget, and M. G. Y a l c i n t a s , 1980. A Combined Methodoloqy f o r E s t i m a t i n s Dose Rates and H e a l t h E f f e c t s f rom Rad ioac t ive P o l l u t a n t s , ORNL/TM-7105, Oak Ridge N a t i o n a l Laboratory , Oak Ridge, TN.
5. EPA, 1987. Gu ide l ines f o r A i r Q u a l i t v Maintenance Planninq and Analys is , Volume 10 (Revised) - Procedures f o r E v a l u a t i n q A i r Q u a l i t v Impact o f New S t a t i o n a r v Sources, EPA-450/4-77-001, U.S. Environmental P r o t e c t i o n Agency, Washington, D.C.
6. R. E. Moore e t a l . , 1979. AIRDOS-EPA: A Computerized Methodoloqy f o r E s t i m a t i n q Environmental Concent ra t ion and Dose t o Man f rom A i rborne Releases o f Radionucl ides, ORNL-5532, Oak Ridge N a t i o n a l Laboratory , Oak Ridge, TN.
7. A. L. S joreen and C. W . M i l l e r , 1984. PREPAR - A User F r i e n d l v Preprocessor t o Create AIRDOS-EPA I n p u t Data Sets, ORNL-5952, Oak Ridge N a t i o n a l Laboratory , Oak Ridge, TN.
APPENDIX D
ATTACHMENTS
ATTACHMENT 1
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FMPC
Radionuclide Air Emission Source
Compi 1 at i on
May 29, 1990
.
* - Contibution Insignificant
SPCIS - Single Point Continuoua Isokinetic Sampler
MPCIS - Multiple Point Continuous Isokinetic Sampler
EC - Engineering Calculation
ATTACHMENT 2
1989 URANIUM EMISSIONS INVENTORY
000063
1989 Uranium Emissions Inventory
I . 1989 Monitored Stack Emissions
Plant 5 65-247 0.004520 65 -248 0.002939 65 - 249 0.01 1035 65-250 ' 0.023766 65-254 0.0081 11 65-267 0.007035 65 - 256 0.004660 65-260 0.071 148 65-261 0.110940 65-262 0.010614 655E- 100 0.001 193 G5A-100 0.059405 G5A-101 0.020661 E. Mold Cooling Booth 0.001565 Graphite Breakup Booth 0.002624
SUB - TOTAL 0.340216 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1989 Uranium Emissions
11. 1989 Scrubber Emissions
1989 Uranium Emissions
1989 Uranium Process Emissions Unmonitored Stacks
P1 ant Source w/o rounding . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Plant 5 East Rockwell Air
Cool i ng We1 1 West Rockwell Air Cool i ng We1 1 East Jolter Muffler 0.0000265 West Jolter Muffler 0.0000265 Breakout Jolter Muffle 0.000000115 Remelt Fce. Hilco Oil Recl amat i on 0.0000744
111.
Kg Uranium
0.000144
0.000144
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Total 0.000415515
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1989 Uranium Emissions
I 1 . 1989 Uranium Emissions fr m Building Vents
V. 1989 Uranium Emissions from Laboratories
VI. 1989 Waste Pit Emissions
VII. 1989 Accidental Uranium Releases
IX. Total Uranium Emissions
Total 1989 FMPC U excluding Accidental Releases 29.7 kg
Total 1989 FMPC U including Accidental Releases 30.1 kg
ATTACHMENT 3
RADIONUCLIDE AIR EMISSIONS
BY GROUPINGS USED FOR
AIRDOS/DARTAB MODELING
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ATTACHMENT 4
A I R EMISSIONS ANNUAL REPORT
PROVIDED TO USEPA HEADQUARTERS BY DOE
TO DEMONSTRATE COMPLIANCE WITH
40 CFR 61, SUBPART H
000071
7442 U.S. Gepartmcnt of Ecergy
Air E m i s s i o n s Annual Repoxt, 40 CFR 6 1 . 9 4 Calendar Y e a r 1599
Site f i j m c : ___- Feed Materials Production -- Center --- I-----
Operations Office Information
Office: Oak Ridge Operations
Address: P.O. Box E
Oak Ridge, TN 37831
Icontact: We1 don Di 11 ow Phone : FTS 626-1354
S i t e Information
Operator:
Address : P.O. Box 398705
Department of Energy - Feed Materials Production Center
Cinc inna t i , O h i o 45239-8705
:ontact: Behram Shroff Phone: FTS 774-6003
Description of Site and Radioactive Materials Handled
The primary a c t i v i t y of the Feed Materials Production Center (FMPC) i s t h t manufacture of p u r i f i e d uranium-metal products. The s i t e reprocesses uranium scrap metal and uranium t r iox ide (UO3) . Uranium hexafluoride (UFg) and uranium t e t r a f l u o r i d e (UFq) are a l so handled and processed a t the FMPC. Radioactive mater ia ls handled and s tored a t the FMPC include pi tch blende ore res idues containing radium stored in t h e K-65 S i l o s , thorium and thorium compounds stored in several locat ions within the FMPC production a rea , uranium metal, uranium compounds, contaminated magnesium f lo ru ide (MgFZ), and contaminated scrap metal.
000072
U-234 0.00495 Th - 228 0.000086 7 U-235 0.000572 Th-230 0.00362 U-236 0,000426 Th-232 0.000032 7 U-238 0.00989 Th-234 0.0162 9 - 9 0 0.0000 148 Pa -234m 0.0162 Tc -99 0.00087 Np-237 0.00000589 Ru-106 0.0000701 PU -238 0.00000240 CS-137 0.0000492 Pu-239 Ba-137m 0.0000492 Pu-240 Ra-226 0.000193 Pu-241 Ra-228 0.0000293 Pu-242 0.00000000258
~- --_-____-_-- _____I-
Methology for Dose Assessment -l__l_-_ --_---
Indicate the methods used in addition to AIRDOS-€PA and RADRISK f o r evaluating doses from the air e m i s s i o n s
- Ambient A i r Monitoring and Dose Assessment
- Thermoluminescent Dosimetry an2 Dose Assessment
I_ CAP-88 (AIRDOS/NRISK with e f f e c t i v e dose equivalent
- X O t h e r ( e x p l a i n ) AIRDOS-EPA, DARTAB and RADRISK
Location of Receptor ( f o r each method, if different)
Distance and direction from release points: The maximally exposed off-site individual i s located 1150 meters north of the center of the FMPC.
Receptor/Use (i.e. residence, school, business)
Residence
Coments/qual i fications: Approximately 93% of the estimated o f f - site dose was contributed by the estimated fugitive emissions from the FMPC waste pits. reference, "Method for Estimating Fugitive Particulate Emissions from Hazardous Waste Sites", USEPA, Cinti, OH, August 1987, EPA/600/2-87/066.
The waste pit emissions were estimated by the methods in the
Whole body dose equivalent cc;;lmitzc~~t: 0.0037 mrern
b. Internally-Deposited Radionuclfdes - (all a i r pathways) - EPA Air Emission Standard: 75 nxem
LUNG 1 : 34 mren Organ # 1 ( mi-ern
Organ # 3 ( RED BONE MARROW ) : 2.2 mrm 0.1- m r e m Organ # 4 ( L I V E R
Organ #2 ( ENDOSTEA~NE) : 2 7-
) : ---
c. Effective Dose Equivalent (CkP-88/AIRDOS if available) - EPA Air Emission Standard: 10 mrem ede
Effective Dose Equivalent: 5.2 m r e m
d. O t h e r (reference methodology and give appropriate units)
Section IV References/Sources of Additional Information
1. 2.
1989 Effluent and Discharge Report, DOE Form 5821 .I Feed Materials Production Center Environmental Monitoring Annual Report for 1989
000074
ATTACHMENT 5
EXAMPLE URANIUM EMISSIONS
CALCULATIONS
000075
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EXAMPLE CALCULATION
Uranium Emission Inventory Group I. 1989 Monitored Stack Emissions
The method for calculating the emission consists of multiplying the milligrams (mg) of uranium on a stack sampler filter as measured by the FMPC Laboratory by a conversion factor and dividing by 1000.
mg U * Conversion Factor (kg/g) * lg/1000mg = kg U
The Conversion Factor (CF) is calculated by:
Stack Area (sq ft)*Average Stack Velocity (ft/min)*( lkg/1000g)
Sample Nozzle Area (sq ft)*Sample Nozzle Velocity (ft/min) CF = . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Dust Collector 643-29 is located in Plant 8. isokinetic stack sampler.
It is equipped with a single point
The CF for Dust Collector 643-29 for 1989 is 3.80 kg/g.
Example Calculation for Sampling Period 1/5/89 to 2/3/89.
1.80 mg U on Filter * 3.80 kg/g "1 g/lOOO mg = 0.00684 kg uranium emitted.
Sampl i ng Uranium on Uranium Emissions Interval Filter (mq) (ks)
1/5/89 to 2/3/89 1.80 0.006840 2/3/89 to 2/7/89 0.07 0.000266 2/7/89 to 2/13/89 0.38 0.001444 2/13/89 to 3/11/89 0.88 0.003344 3/11/89 to 4/8/89 0.22 0.000836 643-29 did not operate for rest of 1989. Total 1989 Uranium Emissions from 643-27 0.012730 kg
5 - - EXAMPLE CALCULATION
Uranium Emission Inventory Group 11. 1989 Scrubber Emissions, Group 111. 1989 Uranium Process Emissions Unmonitored Stacks and Group IV. 1989 Uranium Emissions from Building Vents
Emissions are estimated for the equipment in these groups by the same general methodology. The method for calculating the emissions consists of multiplying an emission factor by an operating parameter such as the operating hours of the source. The emission factor has units of kg of uranium per unit of operation. Some of the emission factors have been developed based on USEPA Method 5 stack testing and some have been developed based on engineering estimates.
As an example the emissions for the Rotary Kiln are estimated. An emission factor for the Rotary Kiln in kg U per hour of operation has been determined based on USEPA Method 5 stack testing. The equation is shown below.
Operating Hours * Emission Factor (Kg U/Hour operation) = kg U emitted
Example Calculation for the Rotary Kiln
The 1989 Emission Factor the Rotary Kiln is 0.00101 kg U/hour of operation.
The Rotary Kiln Operated 22 hours in March, 1989.
22 hours * 0.00101 kg U/hr = 0.02222 kg Uranium Emitted during March.
1989 Rotary Kiln Emissions
Month Operatinq Hours kq U Emitted
January 0 0 February 0 0 March 22 0.02222 Apri 1 0 0 May 157 0.15857 June 388 0.39188 July 12 0.01212 August 0 0 September 0 0 October 0 0 November 0 0 December 0 0 1989 Rotary Kiln Emissions 0.58479 kg
000077
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e 1 4 4 9 EXAMPLE CALCULATION
Uranium Emission Inventory Group VI.
References
1) Reasonably Available Control Measures (RACM) for Fugitive Dust Sources, Ohio EPA, September, 1980.
2) Method for Estimating Fugitive Particulate Emissions from Hazardous Waste Sites, U.S. Environmental Protection Agency, Cincinnati, OH, August 1987.
1989 Waste Pit Emissions
EPA/600/2-87/066.
1989 Emissions from Waste Pits
The equations used for estimation of fugitive emissions from the waste pits are the same as used for the 1988 emissions.
From historical information about quantities of materials stored in the pits, the following estimates of uranium concentration in weight % is assumed for the calculation of emissions.
Pit 5 %U = 0.0569% Pit 6 %U = 9.1%
From Reference 2, pg 37
EW = 0.05 (S/1.5)(d/235)(f/15)(D/90)
where Ew = emission factor, (lb/ton of material stored) S = silt content of stored material, (%) d = dry days per year, (rainfall ~0.01 inch)
f = time that windspeed exceeds 12 mph, (%)
0 = duration o f storage, (days)
d = 248; FMPC meteorological data for 1989
f = 14%; FMPC meteorological data for 1989
Ew is converted to an emission rate by changing the coefficient to 1.7 and deleting the "D/90" term.
Thus
EW = 1.7 (S/1.5)(d/235)(f/15)
where Ew = emission rate, (lbs/acre of storage/day)
Substituting
EW = 1.7 (S/l.5)(248/235)(14/15)
Particulate Emissions lbs/yr
Uranium Emissions = Particulate Emissions lbs/yr x (%U/lOO)(lkg/Z.Z lbs)
= (Ew 1 bs/acre/day) (365 days) (area pit ft2) (1 acre/43,560 ft2)
1 4 4 2 Uranium Emission Inventory Group VI. 1989 Waste Pit Emissions - cont'd Wind Erosion
Exposed Silt Part i cul ate Percent Urani um - Pit Area ft2 Content Ew lbs/acre/day lbs/vr Urani urn k d y r 5 27490 10% 11.163 2571.3 0.0569% 0.67 ,
6 4860 10% 11.163 454.6 9.1% 18.8 Total = 19.47 kg/yr
Note: Pit 4 was covered during 1989.
000079
ATTACHMENT 6
EXAMPLE RADIONUCLIDE EMISSIONS
CALCULATIONS
EXAMPLE RADIONUCLIDE EMISSIONS ESTIMATES c
Group B. Radionuclide Emissions Estimates - Monitored Stack Emissions, Unmonitored Stacks, Building Vents, Laboratories, and Solid Spill
Emissions for Plant 1 are shown below as an example calculation using the uCi/kg U values from Table 5.
Plant 1 kg u Plant 1 kg u Dust Coll ectors 0.017267 Dust Coll ectors 0.01 7267 Plt 1 Build Vent 0.0446 Plt 1 Build Vent 0.0446
Total 0.061867 Total 0.06 1867 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Plant 1 - Dust Collectors Plant 1 - Building Vents kg U = 0.017267 kg U = 0.0446 Isotope uCi/kg U Ci/yr Isotope uCi/kg U Ci/yr . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - - - - - - - - - - - - - - - U234 U235 U236 U238 SR90 TC99 RU 106 CS137 BA137M RA226 RA228 TH228 TH230 TH232 TH234 PA234M NP237 PU238 PU239 PU240 PU241 PU242
298.6 15.8 11.6
333.6 1.76
36.94 6.86 5.13 5.13 0.212 0.85 8.97 26.4 1.41 1319 1319
0.107 0.127 0.839 0.214 3.125
0.0000466
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U234 U235 U236 U238 SR90 TC99 RU106 CS137 BA137M RA226 RA228 TH228 TH230 TH232 TH234 PA234M NP237 PU238 PU239 PU240 PU241 PU242
kg U/yr * uCi/kg U * 1 Ci/l,OOO,OOO uCi = Ci/yr
Example for U234 for Plant 1 Dust Collectors
298.6 15.8 11.6
333.6 1.76
36.94 6.86 5.13 5.13
0.212 0.85 8.97 26.4 1.41 1319 1319
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0.0000466
1.33E-05 7.05E-07 5.17E-07 1.49E-05 7.85E-08 1.65E-06 3.06E-07 2.29E-07 2.29E-07 9.46E-09 3.79E-08 4.00E-07 1.18E-06 6.29E-08 5.88E - 05 5.88E - 05 4.77E-09 5.66E-09 3.74E-08 9.54E-09 1.39E-07 2.08E- 12
0.017267 kg U/yr * 298.6 uCi/kg U * 1 Ci/l,OOO,OOO uCi = 5.16 x 10-6 Ci/yr
Group C.
Example emissions estimates f o r Plant 8 a r e shown below as an example calculat ion using the uCi/kg U values from Table 6 .
Listed below a r e the uCi/kg emission f a c t o r s f o r the Plant 8 Calciner and Rotary Kiln and the uranium emissions from the Plant 8 sources in kg/yr.
Radionuclide Emissions Estimates - Plant 8 Sources
Plant 8 kg u Dust Coll e c t o r s 0.24715 P l t 8 Scrubbers 3.75063 P l t 8 Process 0.013793 P l t 8 Build Vent 0.0349
Plant 8 Calciner kg U = 3.16584 Isotope uCi/kg U
U234 U235 U236 U238 SR90 TC99 RU 106 CS137 BA137M RA226 RA228 TH228 TH230 TH232 TH234 PA234M NP237 PU238 PU239 PU240 PU241 PU242
392.2 19.2
25 332.9
0.0951 36.94
6.86 0.5 0.5
0.00979 0.028
0.0268 0.815 0.016 276.1 276.1 0.185 0.156 1.637 0.424 6.295
0.0000861
A weighted average of t l l e 11 c i ner anh
Plant 8 kg u Dust Coll e c t o r s 0.24715 P l t 8 Scrubbers 3.75063 P l t 8 Process 0.013793 P l t 8 Build Vent 0.0349
Plant 8 Rotary Kiln kg U = 0.58479 Isotope uCi/kg U . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . U234 U235 U236 U238 SR90 TC99 RU 106 CS137 BA137M RA226 RA228 TH228 TH230 TH232 TH234 PA234M NP237 PU238 PU239 PU240 PU241 PU242
437.3 20.1 27 .2
332.8 0.0951
36.94 6.86 0.5 0.5
0.00979 0.028
0.0268 0.815 0.016
1027.4 1027.4 0.185 0.156 1.637 0.424 6.295
0.000086 1
i t a ry I i l n emissions f a c t o r s were appl ,ed t o a l i o the r Plant 8 emissions. The estimate; f o r the Plant 8 Process and Building Vent emissions are shown on the following page a s an example.
Group C. Plant 8 Radionuclide Emissions cont'd
Example for U-234
Weighted Ave U-234 uCi/kg U = 399.23189 uCi/kg U
Note: Additional digits that are not significant were carried through intermediate cal cul at i on s . Plant 8 U Plant 8 U
0.24715 Dust Collectors 0.2471 5 Dust Coll ectors Plt 8 Scrubbers 3.75063 Plt 8 Scrubbers 3.75063 Plt 8 Process 0.013793 Plt 8 Process 0.013793 Plt 8 Build Vent 0.0349 Plt 8 Build Vent 0.0349
Plant 8 kg U = I sotope
U234 U235 U236 U238 SR90 TC99 RU 106 cs137 BA137M RA226 RA228 TH228 TH230 TH232 TH234 PA234M NP237 PU238 PU239 PU240 PU24 1 PU242
- - - - - - - -
- Process 0.013793 uCi/kg U Ci/yr
. - - _ - - - - - - - - - - - - - - - - - - - - 399.23189 5.51 E-06 19.340326 2.67E-07 25.343019 3.50E-07 332.88440 4.59E-06
0.0951 1.31E-09 36.94 5.10E-07 6.86 9.46E-08 0.5 6.90E-09 0.5 6.90E-09
0.00979 1.35E-10 0.028 3.86E- 10 0.0268 3.70E-10 0.815 1.12E-08 0.016 2.21E-10
393.24104 5.42E-06 393.24104 5.42E-06
0.185 2.55E-09 0.156 2.M-09 1.637 2.26E-08 0.424 5.85E-09 6.295 8.68E-08
0.0000861 1.19E-12
Plant 8 kg U = Isotope
U234 U23 5 U236 U238 SR90 TC99 RU106 CS137 BA137M RA226 RA228 TH228 TH230 TH232 TH234 PA234M NP237 PU238 PU239 PU240 PU24 1 PU242
- - - - - - - -
- Building Vents 0.0349
uCi/kg U Ci/yr . . . . . . . . . . . . . . . . . . . . . . . 399.23189 1.39E-05 19.340326 6.75E-07 25.343019 8.84E -07 332.88440 1.16E-05
0.0951 3.32E-09 36.94 1.29E-06 6.86 2.39E-07 0.5 1.75E-08 0.5 1.75E-08
0.00979 3.42E- 10 0.028 9.77E-10 0.0268 9.35E-10 0.815 2.84E-08 0.016 5.58E-10
393.24 104 1.37E-05 393.24104 1.37E-05
0.185 6.46E-09 0.156 5.44E-09 1.637 5.71E-08 0.424 1.48E-08 6.295 2.20E-07
0.0000861 3.00E-12
kg U/yr * uCi/kg U * 1 Ci/l,OOO,OOO uCi = Ci/yr
Example for U234 for Plant 8 Rotary Kiln
0.013793 kg U/yr * 399.23189 uCi/kg U * 1 Ci/l,OOO,OOO uCi = 5.51 x 10-6 Ci/yr
Group D. Rad ionuc l i de Emissions Est imates - Waste P i t s
Emissions f o r Waste P i t s a re shown below us ing t h e uCi/kg U va lues f rom Table 7.
Waste P i t 5 kg U = 0.67
I so tope uCi/kg U Ci/yr _ _ _ _ _ _ _ - _ _ - _ - - - - - - - - - - - - - U234 331.8 2.22E-04 U235 17.8 1.19E-05 U236 12.9 8.64E-06 U238 333.3 2.23E-04 SR90 4.15 2.78E-06 TC99 662.5 4.44E-04
CS137 13.5 9.05E-06 BA137M 13.5 9.05E-06 RA226 287.2 1.92E-04 RA228 35.4 2.37E-05 TH228 45.6 3.06E-05 TH230 5135 3.44E-03 TH232 35.4 2.37E-05 TH234 333.3 2.23E-04 PA234M 333.3 2.23E-04 NP237 5.31 3.56E-06 PU238 1.04 6.97E-07 PU239 1.3 8.71E-07 PU240 1.3 8.71E-07 PU24 1 8.8 5.90E-06
RU106 ND 0.00Et00
Waste P i t 6 kg U = 18.8 uCi/kg U Ci/yr _ _ _ _ _ _ _ _ - _ - - _ - - - - _
67 1.26E-03 20.4 3.84E-04 12.9 2.43E-04
332.9 6.26E-03 0.037 6.96E-07
2.49 4.68E-05
0.34 6.39E-06 0.34 6.39E-06
0.01 1.88E-07 0.0186 3.50E-07
0.52 9.78E-06 0.01 1.88E-07
332.9 6.26E-03 332.9 6.26E-03 0.049 9.21E-07 0.015 2.82E-07 0.085 1.60E-06 0.085 1.60E-06
0.58 1.09E-05
ND 0.00Et00
ND ND
kg U/yr * uCi/kg U * 1 C i / l , O O O , O O O uCi = Ci/yr
Example f o r U234 f o r P i t 5
Waste P i t s - To ta l kg U = 19.47 T o t a l Ci/yr - - - - - - - - - - - - - - - - - _
1.48E-3 3.95E-4 2.51E-4 6.48E -3 3.48E-6 4.91E-4
1.54E-5 1.54E-5 1.92E-4 2.39E-5 3.09E-5 3.45E-3 2.39E-5 6.48E-3 6.48E-3 4.48E-6 9.79E-7 2.47E-6 2.47E-6 1.68E-5
ND
0.67 kg U/yr * 331.8 uCi/kg U * 1 C i / l , O O O , O O O uCi = 2.22 x 10-4 Ci/yr
Waste P i t s T o t a l = Ci/yr P i t 5 t Ci/yr P i t 6
Example f o r U234 f o r T o t a l f o r Waste P i t s
Waste P i t s T o t a l = 2.22 x 10-4 Ci/yr t 1.26 x 10-3 Ci/yr = 1.48 x 10-3 Ci/yr
0019084
’., I 4 4 2 Group E. Radionuclide Emissions Estimates - Uranium Metal Fines Fire Emissions for Uranium Fines Fire are calculated below using the uCi/kg U values from Table 8.
U Fire kg U = 0.38 Isotope uCi/kg U Ci/yr . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . U234 186 7.07E-05 U235 4.41 1.68E-06 U236 0.637 2.42E-07 U238 334 1.27E-04 SR90 0.19 7.22E-08 TC99 17 6.46E-06 RUI 06 3.9 1.48E-06 CS137 3.1 1.18E-06 BA137M 3.1 1.18E-06 RA226 0.058 2.20E-08 RA228 0.12 4.56E-08 TH228 9.3 3.53E-06 TH230 2.7 1.03E-06 TH232 2.3 8.74E-07 TH234 2900 1.10E-03 PA234M 1300 4.94E-04 NP237 0.33 1.25E-07 PU238 0.062 2.36E-08 PU239 0.136 5.17E-08 PU240 0.034 1.29E-08
kg U/yr * uCi/kg U * 1 Ci/l,OOO,OOO uCi = Ci/yr
Example for U234 for Uranium Fines Fire
0.38 kg U/yr * 186 uCi/kg U * 1 Ci/l,OOO,OOO uCi = 7.07 x 10-5 Ci/yr